Letter Sequence RAI |
---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
Results
Other: ML083030246, ML083330066, ML083640401, ML090220584, ML090650061, ML090720066, ML090720068, ML090830248, ML090860762, ML090930256, ML091070269, ML091170031, ML091830055, ML091880258, ML101040676, ML101050376, ML101270268, ML102010302, ML102020397, NLS2009099, SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application
|
MONTHYEARML0830302462008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix E, Environmental Report Project stage: Other ML0833300662008-12-19019 December 2008 Determination of Acceptability and Sufficiency for Docketing and Opportunity for a Hearing Regarding the Application from Nebraska Public Power District, for Renewal of the Operating License for the Cooper Nuclear Station Project stage: Other ML0901203602009-01-0909 January 2009 Safety Evaluation Report Project stage: Request ML0836404012009-01-21021 January 2009 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for License Renewal for the Cooper Nuclear Station Unit 1 (TAC No. MD9763 and MD 9737) LTR Project stage: Other ML0906500612009-02-0202 February 2009 Letter from Nebraska State Historical Society Regarding Cooper Nuclear Station License Renewal Project stage: Other ML0907506862009-02-25025 February 2009 Scoping and Process Public Meeting Sides of February 25, 2009 Project stage: Request ML0908400622009-02-25025 February 2009 Transcript of Cooper Nuclear Station License Renewal Pubic Meeting - Evening Session, February 25, 2009, Pages 1-41 Project stage: Meeting ML0908400632009-02-25025 February 2009 Transcript of Cooper Nuclear Station License Renewal Public Meeting - Afternoon Session, Wednesday, February 25, 2009, Pages 1-33 Project stage: Meeting ML0907200662009-02-25025 February 2009 Comment (1) of James Gerweck, on Behalf of the Richardson County, Nebraska, Emergency Management Agency, Supporting CNS License Renewal Project stage: Other ML0907200682009-02-27027 February 2009 Comment (3) of Ashtin Paris, on Behalf of the City of Rock Port, Supporting Nebraska Public Power District'S Cooper Nuclear Station License Renewal Project stage: Other ML0908607622009-03-0909 March 2009 Letter from the Nebraska Department of Natural Resources the Cooper Nuclear Station License Renewal Project stage: Other ML0907200672009-03-10010 March 2009 Comment (2) of Alan Richard, on Behalf of Pawnee City Development Corporation, Supporting Renewal of License for Cooper Nuclear Station Project stage: Request ML0908302482009-04-0303 April 2009 Environmental Site Audit Regarding Cooper Nuclear Station Unit 1 License Renewal Application (TAC MD9763 and MD9737) Project stage: Other ML0902205842009-04-0303 April 2009 Proposed Review Schedule Regarding the Application from Nebraska Public Power District for Renewal of the Operating License for the Cooper Nuclear Station Project stage: Other ML0909302562009-04-0909 April 2009 Audit Plan for Aging Management Program Site Audit Regarding Cooper Nuclear Station Unit 1, License Renewal Application (Tac No. MD9737) Project stage: Other ML0909103082009-04-14014 April 2009 Summary of Public Environmental Scoping Meeting Related to the Review of the Cooper Nuclear Station, Licensed Renewal Application Project stage: Meeting ML0910702692009-04-16016 April 2009 EPA Comment on the Cooper Nuclear Station License Renewal Application Project stage: Other ML0911700312009-04-28028 April 2009 Environmental Site Audit Regarding Cooper Nuclear Station Unit 1 License Renewal Application Project stage: Other ML0909704142009-04-30030 April 2009 Summary of Site Audit Related to the Review of the License Review Application for Cooper Nuclear Station, Unit 1 Project stage: Approval ML0911905972009-05-0101 May 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application (TAC No. MD9763 and MD9737) Project stage: RAI NLS2009039, Response to Request for Additional Information for License Renewal Application - Balance-of-Plant Scoping and Screening2009-05-28028 May 2009 Response to Request for Additional Information for License Renewal Application - Balance-of-Plant Scoping and Screening Project stage: Response to RAI ML0912000172009-05-29029 May 2009 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Application by the Nebraska Public Power District, for Renewal of the Operating License for Cooper Nuclear Station Unit 1 Project stage: Approval ML0917500882009-06-0101 June 2009 CNS Lr - NDEQ 2009 Ambient Network Plan Project stage: Request ML0918300552009-06-0808 June 2009 Reply from Fish and Wildlife Service on Transmission Line for Cooper Nuclear Station License Renewal Project stage: Other ML0915303162009-06-0808 June 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0917501182009-06-11011 June 2009 CNS Lr - Tornado Occurrences in Nemaha County, Ne 1950-2009 Project stage: Request ML0913803652009-06-15015 June 2009 Audit Report Regarding the Cooper Nuclear Station, Unit 1, License Renewal Application Project stage: Acceptance Review NLS2009040, Response to Request for Additional Information for License Renewal Application - Aging Management Programs2009-06-15015 June 2009 Response to Request for Additional Information for License Renewal Application - Aging Management Programs Project stage: Response to RAI NLS2009049, Response to Request for Additional Information for License Renewal Application - Section B and C2009-06-22022 June 2009 Response to Request for Additional Information for License Renewal Application - Section B and C Project stage: Response to RAI ML0916002892009-06-29029 June 2009 Request for Additional Information for Cooper Nuclear Station License Renewal Project stage: RAI ML0916002782009-06-29029 June 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI NLS2009048, Response to Request for Additional Information for License Renewal Application Severe Accident Mitigation Alternatives2009-07-0101 July 2009 Response to Request for Additional Information for License Renewal Application Severe Accident Mitigation Alternatives Project stage: Response to RAI ML0917503682009-07-0101 July 2009 Summary of Regulatory Audit Related to the Review of the License Renewal Application for Cooper Nuclear Station Project stage: Approval ML0918802582009-07-0808 July 2009 Environment Project Manager Change for the License Renewal of Cooper Nuclear Station Project stage: Other ML0918804782009-07-14014 July 2009 Request for Additional Information Project stage: RAI ML0919005022009-07-14014 July 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0918804822009-07-14014 July 2009 Request for Additional Information for the Review of Cooper Nuclear Station License Renewal Application Project stage: RAI ML0918702982009-07-16016 July 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0918703042009-07-16016 July 2009 License Renewal Request for Additional Information Project stage: RAI ML0921600842009-07-20020 July 2009 Notice of Diane Curran'S Withdrawal of Appearance Project stage: Request ML0920902762009-07-29029 July 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application (TACs MD9763 and MD9737) Project stage: RAI NLS2009055, Response to Request for Additional Information for License Renewal Application2009-07-29029 July 2009 Response to Request for Additional Information for License Renewal Application Project stage: Response to RAI NLS2009063, Response to Request for Additional Information for License Renewal Application2009-08-17017 August 2009 Response to Request for Additional Information for License Renewal Application Project stage: Response to RAI ML0919600402009-08-19019 August 2009 Summary of Regulatory Audit Related to the Review of the License Renewal Application for Cooper Nuclear Station Project stage: Approval ML0923106542009-08-28028 August 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0926500572009-09-28028 September 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0926809352009-10-0707 October 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0927300142009-10-15015 October 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI NLS2009085, Response to Request for Additional Information on License Renewal Application2009-10-22022 October 2009 Response to Request for Additional Information on License Renewal Application Project stage: Response to RAI ML0929200192009-10-29029 October 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI 2009-04-09
[Table View] |
|
---|
Category:Letter
MONTHYEARML24227A0822024-09-0303 September 2024 Summary of Regulatory Audit in Support of License Amendment Request to Modify the High Pressure Coolant Injection Low Flow Value IR 05000298/20240052024-08-22022 August 2024 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2024005) IR 05000298/20240022024-07-25025 July 2024 Integrated Inspection Report 05000298/2024002 ML24183A1722024-07-17017 July 2024 Issuance of Amendment No. 277 to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML24197A1462024-07-15015 July 2024 NRC Region IV Ltr to Cooper Nuclear Station Re FEMA Level 1 Finding IR 05000298/20243012024-07-12012 July 2024 NRC Examination Report 05000298/2024301 ML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 ML24197A0682024-06-24024 June 2024 FEMA Ltr to Missouri State Emergency Management Agency - Level 1 Finding, 24 June 2024 ML24192A0112024-06-13013 June 2024 2024-06-Post Exam Comments IR 05000298/20244012024-06-0404 June 2024 Security Baseline Inspection Report 05000298/2024401 ML24151A1082024-05-30030 May 2024 NRC Initial Operator Licensing Examination Approval 05000298/2024301 ML24137A0942024-05-17017 May 2024 Regulatory Audit Plan in Support of License Amendment Request to Modify Allowable Value Regarding Technical Specification for High Pressure Coolant Injection Pump Discharge Low Flow IR 05000298/20240012024-05-0303 May 2024 Integrated Inspection Report 05000298/2024001 ML24129A0952024-04-25025 April 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000298/20240102024-04-24024 April 2024 Comprehensive Engineering Team Inspection Report 05000298/2024010 ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) ML24093A2282024-04-0202 April 2024 Notice of Enforcement Discretion for Cooper Nuclear Station IR 05000298/20240902024-04-0101 April 2024 – Notice of Violation, NRC Inspection Report 05000298/2024090 IR 05000298/20230062024-02-28028 February 2024 Annual Assessment Letter for Cooper Nuclear Station - Report 05000298/2023006 IR 05000298/20230042024-02-12012 February 2024 Integrated Inspection Report 05000298/2023004 ML24033A3092024-02-12012 February 2024 Summary of Regulatory Audit Regarding the Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20230122024-02-12012 February 2024 NRC Inspection Report 05000298/2023012 ML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23311A1122023-11-0909 November 2023 Project Manager Assignment IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report ML23102A0282023-04-19019 April 2023 U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting IR 05000298/20230012023-04-17017 April 2023 Integrated Inspection Report 05000298/2023001 ML23060A1582023-03-0808 March 2023 Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001 IR 05000298/20220062023-03-0101 March 2023 Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006 ML23041A1622023-02-10010 February 2023 Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information IR 05000298/20220042023-01-30030 January 2023 Integrated Inspection Report 05000298/2022004 IR 05000298/20220112022-12-23023 December 2022 License Renewal Phase 4 Inspection Report 05000298/2022011 ML22286A2072022-11-30030 November 2022 Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements IR 05000298/20220032022-10-27027 October 2022 Integrated Inspection Report 05000298/2022003 ML22304A0052022-10-26026 October 2022 Surveillance Capsule Location (Re-insertion Into the Reactor Vessel) IR 05000298/20223022022-10-20020 October 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022302 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information 2024-09-03
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24094A2462024-04-0303 April 2024 NRR E-mail Capture - Cooper Nuclear Station - RAI Emergency LAR Turbine Stop Valve Limit Switch TS 3.3.1.1 ML24032A2382024-02-0101 February 2024 NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance ML24010A1172024-01-10010 January 2024 NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance ML24010A0902024-01-0404 January 2024 RAI - 10120-R1 - Final Dfo Tank Inspections LAR ML23352A2472023-12-18018 December 2023 NRR E-mail Capture - Cooper Nuclear Station - Relief Request RC3-02 Drywell Head Inspection RAI Issuance ML23257A2192023-09-14014 September 2023 NRR E-mail Capture - Cooper - Final RAI LAR to Adopt TSTF-551, Revision 3 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information ML22208A0642022-07-26026 July 2022 Notification of Inspection and Request for Information for NRC Inspection Report 05000298/2022004 ML22179A3152022-06-28028 June 2022 Notification of Post-Approval Site Inspection for License Renewal (Phase 4) (NRC Inspection Report 05000298/2022011) and Request for Information ML22010A2632022-01-10010 January 2022 NRR E-mail Capture - Cooper - Final RAI Relief Request RR5-01 Revision 1 ML21321A3742021-11-10010 November 2021 NRR E-mail Capture - Cooper - Final RAI Alternative Request RI5-02 Revision 3 ML21258A2632021-09-15015 September 2021 NRR E-mail Capture - Cooper - Final RAI Alternative Request RS-01 ML21109A2222021-04-15015 April 2021 Email with RFI Document for CNS PIR 2021012 ML21026A3112021-01-27027 January 2021 Notification of NRC Design Bases Assurance Inspection (Team) (NRC Inspection Report 05000298/2021010) and Initial Request for Information ML20315A3922020-11-10010 November 2020 Email 11-10-2020 - Cooper EP Prog Insp RFI ML20203M3692020-07-21021 July 2020 NRR E-mail Capture - Cooper - Final RAI License Amendment Request for Approval of EAL Scheme Change (EPID L-LLA-2020-0028) ML18306A5582018-10-30030 October 2018 Notification of Cyber Security Inspection(Nrc Inspection Report 05000298/2019410) and Request for Information ML18060A0272018-02-28028 February 2018 Enclosurequest for Additional Information (Letter to J. Shaw Request for Additional Information Regarding Nebraska Public Power District'S Decommissioning Funding Plan Update for Cooper Nuclear Station ISFSI) ML18037B0002018-02-0606 February 2018 NRR E-mail Capture - Cooper Nuclear Station - Final RAI Relief Requests RR-02 and RR-03 (EPIDs L-2017-LRR-065 and -066) ML18025C0042018-01-25025 January 2018 Notification of NRC Design Bases Assurance Inspection (Teams) (05000298/2018011) and Initial Request for Information ML18024A3752018-01-24024 January 2018 NRR E-mail Capture - Cooper Nuclear Station - Final RAI LAR to Adopt TSTF-542 (CAC MG0138; EPID L-2017-LLA-0290) IR 05000298/20170032017-11-13013 November 2017 NRC Integrated Inspection Report 05000298/2017003 and Independent Spent Fuel Storage Installation Inspection Report 07200066/2017001 ML17177A2432017-06-26026 June 2017 Notification of NRC Design Bases Assurance Inspection (Programs) (05000298/2017007) and Initial Request for Information ML17024A3292016-12-15015 December 2016 NRR E-mail Capture - Rec 2.1 Seismic: Cooper'S SFP Evaluation ML16335A0152016-11-29029 November 2016 NRR E-mail Capture - Cooper Nuclear Station - Formal Request for Additional Information Concerning License Amendment Request to Adopt TSTF-425 Revision 3 ML16112A2732016-04-21021 April 2016 Notification of NRC Triennial Fire Protection Baseline Inspection (05000298/2016008) and Request for Information ML15107A2542015-05-0404 May 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report ML15051A4872015-02-20020 February 2015 Notification of NRC Component Design Bases Inspection 05000298/2015007 and Initial Request for Information ML13323A1052013-12-0404 December 2013 Interim Staff Evaluation and Request for Additional Information, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13256A0822013-09-12012 September 2013 Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13246A3482013-08-29029 August 2013 Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NLS2013082, Letter Requesting Information from the United States Army Corps of Engineers to Provide Response to March 12, 2012 Letter Regarding Enclosure 2, Recommendation 2.1, Flooding2013-08-22022 August 2013 Letter Requesting Information from the United States Army Corps of Engineers to Provide Response to March 12, 2012 Letter Regarding Enclosure 2, Recommendation 2.1, Flooding ML13155A0112013-06-0303 June 2013 Request for Additional Information Email, 2013 Decommissioning Funding Status Report ML13133A0802013-05-24024 May 2013 (Redacted) - Request for Additional Information, Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts ML13144A5202013-05-24024 May 2013 Request for Additional Information Email, Decommissioning Funding Status Report ML13095A1602013-04-0404 April 2013 Email, Draft Request for Additional Information - Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts ML13059A3452013-03-0808 March 2013 Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation ML13053A3422013-02-22022 February 2013 E-mail, Draft Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation ML12338A2642012-12-0303 December 2012 Email, Round 3, Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and SRs ML12312A2812012-11-14014 November 2012 Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12283A4002012-10-0909 October 2012 Email, Draft Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA)-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12251A0582012-09-0606 September 2012 Request for Additional Information, License Amendment Request, Round 2, Revise Technical Specifications to Implement a 24-Month Fuel Cycle and Adopt TSTF-493, Revision 4, Option a ML12235A2522012-09-0505 September 2012 Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio ML12205A2162012-08-10010 August 2012 Request for Additional Information, Round 2, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements ML1217400512012-06-21021 June 2012 List of Questions for Supplement to Complete Acceptance Review, License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12159A2992012-06-11011 June 2012 Request for Additional Information, Relief Request RI-07 from ASME Code Requirements for Residual Heat Removal Shell Circumferential and Nozzle to Head Welds, Fourth 4th 10-Year Inservice Inspection Interval ML12157A5412012-06-11011 June 2012 Second Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Value Inservice Testing Program ML12153A0642012-05-31031 May 2012 Notification of Inspection (NRC Inspection Report 05000298/2012005) and Request for Information ML1213905092012-05-18018 May 2012 Email, Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval 2024-04-03
[Table view] |
Text
October 29, 2009
Mr. Stewart B. Minahan Chief Nuclear Officer, Vice President - Nuclear Cooper Nuclear Station Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO.
MD9763 AND MD9737)
Dear Mr. Minahan:
By letter dated September 24, 2008, Nebraska Public Power District submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the Operating License No. DPR-46, for Cooper Nuclear Station for review by the U.S. Nuclear Regulatory Commission (or the staff). The staff is reviewing the information contained in the license renewal application and the associated Environmental Report submitted. The staff has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Mr. David Bremer. A mutually agreeable date for the response is within 30 days from the date of this letter, in order to maintain the license renewal review schedule. If you have any questions, please contact me at 301-415-3617 or by e-mail at Tam.Tran@nrc.gov, or Bennett Brady at 301-415-2981 or by e-mail at Bennett.Brady@nrc.gov. Sincerely, /RA/
Tam Tran, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation
Docket No. 50-298
Enclosure:
As stated
cc w/encl: See next page
ML092940414 OFFICE PM:DLR:RPB1 LA:RPOB:DLR PM:DLR:RPB2 BC:DLR:RPB1 PM:DLR:RPB1 NAME BBrady SFigueroa TTran BPham TTran (Signature) DATE 10/26/09 10/26/09 10/28/09 10/29/09 10/29/09 Letter to Stewart. B. Minahan from Tam Tran dated October 29, 2009
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO.
MD9763 AND MD9737)
DISTRIBUTION
E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource
T. Tran B. Brady F. Lyon I.Couret D. Roth (OGC)
A. Jones (OGC)
N. Taylor (RIV)
E. Collins (RIV)
C. Casto (RIV)
B. Maier (RIV)
V. Dricks (RIV)
D. Chamberlain (RIV)
A. Vegel (RIV)
W. Walker (RIV)
G. Miller (RIV)
G. Pick (RIV))
Cooper Nuclear Station
cc:
Mr. Ronald D. Asche President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601
Mr. Gene Mace Nuclear Asset Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321
Mr. John C. McClure Vice President and General Counsel Nebraska Public Power District P.O. Box 499 Columbus, NE 68602-0499
Mr. David Van Der Kamp Licensing Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321
Mr. Michael J. Linder, Director Nebraska Department of Environmental Quality P.O. Box 98922 Lincoln, NE 68509-8922
Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305
Ms. Julia Sc hmitt, Manager Radiation Control Program Nebraska Health & Human Services R&L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007
Deputy Director for Policy Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176
Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 218 Brownville, NE 68321
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125
Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116
Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366
Ms. Melanie Rasmussen Radiation Control Program Director Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319
Mr. Keith G. Henke, Planner Division of Community and Public Health Office of Emergency Coordination 930 Wildwood Drive P.O. Box 570 Jefferson City, MO 65102
Cooper Nuclear Station
cc:
Mr. Art Zaremba, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321
Mr. John F. McCann, Director Licensing, Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601-1813
Mr. Mike Boyce Cooper Strategic Initiatives Manager Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321
Mr. Dave Bremer License Renewal Project Manager Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321
Mr. Bill Victor License Renewal Project Licensing Lead Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321
Mr. Garry Young License Renewal Manager Entergy Nuclear 1448 S.R. 333, N-GSB-45 Russellville, AR 72802
Mr. Alan Cox License Renewal Technical Manager Entergy Nuclear 1448 S.R. 333, N-GSB-45 Russellville, AR 72802 Mr. Dave Lach LRP Entergy Project Manager Entergy Nuclear 1448 S.R. 333, N-GSB-45 Russellville, AR 72802 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION
RAI 2.3.3.12 AR-4 Air Removal System
Background
Title 10 of the Code of Federal Regulations Part 54.21(a)(1) (10 CFR 54.21(a)(1)) requires the applicant to provide a list of structures and components subject to an aging management review (AMR). Issue a) In RAI 2.3.3.12 AR-2, dated July 16, 2009, the staff identified in the Updated Safety Analysis Report (USAR), a safety function for main steam line high radiation signal immediately tripping the mechanical vacuum pumps and closing the pumps' inlet and outlet valves in the event of a dropped rod accident. The license renewal application (LRA) does not identify this function under the air removal (AR) system nor do the LRA drawings highlight the flow path. In its response, dated August 17, 2009, the applicant stated that the isolation valves for the mechanical vacuum pumps have an intended function of isolating the vacuum pumps from the main condenser in the event of a dropped rod accident. The applicant added the function to the LRA for the AR system. However, the applicant excluded the isolation valve for the scope of license renewal based on the valve function being completed with moving parts, and the passive pressure boundary provided by the valve bodies was not required to prevent the vacuum pumps from actively discharging air from the condenser through the elevated release point (ERP).
Therefore, the applicant's position is that the valves are not subject to an AMR.
The staff does not agree with the applicant's rational, which excludes the isolation valves from the scope of license renewal and subject to an AMR. In accordance with 10 CFR 54.21, valve bodies are long-lived, passive components that are subject to an AMR. The valve's bodies are an integral part of the pressure boundary and are required to perform the isolation function. In addition, the piping from the condenser to the valves and the associated components are part of the pressure boundary and are required to perform the isolation function; therefore, they also should be included in scope as passive, long-lived components and subject to an AMR.
b) In RAI 2.3.3.12-AR-3, a similar issue was identified with the steam jet air ejectors. In the response, the applicant correctly included part of the flow path and valves 'from' the turbine building to the off-gas (OG) building in scope of license renewal and subject to an AMR, but the applicant did not include the flowpath 'inside' the turbine building. The piping and components inside the turbine building are necessary to provide a pressure boundary function to isolate the condenser on a high radiation signal. Request a) The applicant needs to include the passive, long-lived components necessary to isolate the flow path up to and including the isolation valves for the mechanical vacuum pumps in the scope of license renewal in accordance with the requirement as stated in 10 CFR 54.21; or provide an adequate justification, that is in accordance with the requirements stated in 10 CFR 54.21, for not including the above described components.
b) The applicant needs to include the long-lived components from the isolation valves on piping 12" AR-2 up to and including 16" AR-2 holdup line in the scope of license renewal in accordance with the requirement as stated in 10 CFR 54.4(a) or provide an adequate justification why a failure of this piping will not cause a loss of the pressure boundary function on 16' AR-2.
c) The applicant needs to include the passive piping and components upstream of piping 48" AR-1 to the condenser in the scope of license renewal in accordance with the requirements as stated in 10 CFR 54.4(a), or provide an adequate justification why a failure of this piping will not cause a loss of the pressure boundary function.
RAI 2.3.3.12 OG-9 Off-gas System
Background
10 CFR 54.21(a)(1) requires the applicant to provide a list of structures and components subject to an AMR.
Issue:
In RAI 2.3.3.12 OG-5, dated July 16, 2009, the staff noted in LRA Section 2.3.3.12 for the OG system the applicant includes several piping runs with instrumentation in the off-gas building in scope of license renewal and highlighted orange on LRA Drawing 2037, indicating the piping is in scope in accordance with 10 CFR 54.4(a)(1). Yet the fluid-filled oil system in the OG building that supports the OG system is not shown as in scope of license renewal. The staff requested the applicant justify the exclusion of the oil system components from the scope of license renewal. In its response to RAI 2.3.3.12 OG-5, dated August 17, 2009, the applicant stated that orange highlighted piping to OG-DPT-550 and OG-DPIS-550 was in scope for a functional (a)(2) not (a)(1) as a pressure boundary for the safety-related instruments OG-DPT-114 and OG-DPIS-114. Therefore, the applicant position is that there are no safety-related components in the OG building; hence, the oil system components are not required to be included in scope of license renewal.
The staff disagreed with the applicant's response to RAI 2.3.3.12 OG-5. The staff noted that part of the piping to pressure instruments OG-DPT-550 and OG-DPIS-550 included piping to monitor and equalize the vacuum between the OG 48" hold up line and the Z sump. This function is described in USAR Chapter IX, Section 4.5.1 as having the capability to interfere with post-accident Z sump operation. The applicant identified these monitoring instruments as safety-related, but did not identify their location, which appears to be in the OG building. Also along with the monitoring as a safety-related function, the equalization line should be safety- related as well. From LRA Drawing 2037, the 3/4" equalization line appears to be in the OG building as well. Having these safety-related components in the OG building contradicts the applicant's information provided in the RAI response that there are no safety-related components in the OG building.
Request: a) Examine whether there are safety-related components in the OG building, to include the instruments used to monitor the pressure in the sump, and the equalization line from the Z sump to the holdup line for inclusion in scope under 10 CFR 54.4(a)(1), and perform an evaluation of nonsafety-related components for inclusion in scope under 10 CFR 54.4(a)(2).
b) Amend the LRA to add the (a)(1) functions for monitoring and equalizing the sump with the hold up line, that were identified in RAI 2.3.3.12 OG-7 or provide adequate justification otherwise.
RAI 2.3.3.12 OG-10 Off-gas System
Background
10 CFR 54.21(a)(1) requires the applicant to provide a list of structures and components subject to an AMR.
Issue:
In RAI 2.3.3.12 OG-7, dated July 16, 2009, the staff noted in the LRA Section 2.3.3.12 there were functions identified for the OG system under 10 CFR 54.4(a)(1), indicating that the OG system contained safety-related components. The staff requested the applicant identify the safety-related components in the OG system and the safety function they provide. In its response to RAI 2.3.3.12 OG-7, dated August 17, 2009, the applicant identified the safety function that OG system performs is venting the Z sump to the ERP, and monitoring and equalizing the vacuum between the 48" hold-up line and the Z sump. The applicant provided a list of the identification number of the safety-related valves and their location on LRA Drawings 2037 and 2005 sheet 2.
The staff does not agree that the list was comprehensive to include all the safety-related components in the OG system. The applicant supplied a list of the safety-related valves in the OG system from their database. However, the applicant did not provide any piping line numbers. There are several runs of piping that do not have valves; therefore the staff can not positively identify the lines that are safety-related. In addition, there are other valves not on the list provided that appear to be on safety-related lines.
Example: on LRA Drawing 2005 sheet 2 there are two drain lines from the ERP to the Z sump.
The list provided by the applicant includes OG-113, hence indicating that line 1 1/2" FDR-2 is safety-related; however, the redundant line 1 1/2" FDR-2 that is heat-traced contains valve OG-104, which was not included on the list of safety-related valves in the OG system. Request:
Perform a more in-depth review of the OG system not relying solely on using their component database system and provide a complete list of safety-related components, to include piping, in order for the staff to ensure that the applicant did not omit any components from the scope of license renewal.
RAI 2.3.3.12 PD-4 Plant Drains
=
Background===
During the plant walkdown, the staff noted that there was turbine building roof drain piping located in areas of the plant containing system, structure, and components (SSCs) in the scope for license renewal under the applicability of 10 CFR 54.4(a)(1).
In addition to the turbine building roof drains, the staff noted there was black drain pipe on the back wall in the emergency battery room, which could not be positively identified as to what system it belonged to and if it was properly identified as in scope for license renewal.
The staff could not identify an LRA section describing the roof drains or LRA drawings that show the flow path of the roof drains except for LRA drawing 2038 SH 1, which shows some reactor building roof drains.
Issue:
10 CFR 54.21 requires each applicant to describe and justify the methods used to identify and list those structures and components subject to an AMR. The staff saw turbine building roof drain piping in an area with 10 CFR 54.4 (a)(1) SSC, but could not find this piping accounted for in the LRA, including the LRA drawings. Furthermore, the drain pipe in the emergency battery room could not be accounted for in the LRA, including the LRA drawings. Additionally the LRA does not mention any roof drains other than on LRA drawing 2038 SH 1. Many buildings contain 10 CFR 54.4 (a)(1) SSC which may have internal roof drain piping. None of this piping is accounted for in the LRA.
Request: a) Justify the exclusion of above mentioned piping from the scope of license renewal under 10 CFR 54.4(a)(2) and subject to an AMR.
b) Identify all roof drains for every building that contains SSC that are in the scope for license renewal under the applicability of 10 CFR 54.4(a)(1) and show which roof drain piping is and is not in scope for license renewal under the applicability of 10 CFR 54.4(a)(2).
RAI 2.3.3.12 PD-5 Plant Drains
=
Background===
The LRA originally listed the RW system function of providing "a barrier to ground level release via the Z sump during accidents where the SGT system must operate" as an intended function for 10 CFR 54.4(a)(1). In response to RAI 2.3.3.12 OG-6 and RAI 2.3.3.12 PD-3, the applicant revised the above stated function to be an intended function for 10 CFR 54.4(a)(2) by explaining that valves RW-V-10 and RW-V-11 and the remaining portion of the flow path to the radwaste building is nonsafety-related with an intended function in accordance with 10 CFR 54.4(a)(2).
USAR Chapter X, Section 14.2 lists the safety design basis of the equipment and floor drainage systems. This section lists two safety design basis. The first safety design basis is to ensure that the Z sump in flows from condensation does not impede the flow of the SGT system to the ERP. The second safety design basis is to provide a barrier to ground level release via the Z sump during accidents where the SGT system must operate.
Issue:
The portion of the piping described in the Background, that provides a barrier to a ground release, is necessary in performing the second safety design basis described above. Yet the applicant has designated this piping to be in scope for license renewal in accordance with 10 CFR 54.4(a)(2) and not 10 CFR 54.4(a)(1).
Request:
Justify why the portion of the piping described in the Background, which provides a barrier to a ground release, is not designated in scope for license renewal in accordance with 10 CFR 54.4(a)(1), since it performs the second safety design basis described in USAR Chapter X, Section 14.2. If the piping is in scope for 10 CFR 54.4(a)(1), SSC in the vicinity needs to be evaluated for in scope 10 CFR 54.4(a)(2).
RAI 2.3.3.10 IA-1 Instrument Air
=
Background===
Drawing 2010 SH 1, Flow Diagram Instrument Air Control & Turbine Building, shows fire protection air accumulators FP Sys 5, 14,8,9,10,11,1A&7, 21,15,16,17,18,19, & 20 among others and associated piping. The accumulators and associated supply air piping and valve bodies are not shown as subject to an AMR.
Issue:
10 CFR 54.4 (a)(3) states that all systems, structures and components relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the commissions regulations for fire protection (10 CFR 50.48) are within the scope of license renewal.
10 CFR 54.21 states that systems structure and components within the scope of license renewal are subject to an AMR if they perform their intended function without moving parts or without a change in configuration or properties and are not subject to replacement based on qualified life or specified time period.
Request:
Explain why the above described system, structure and components are not shown as subject to an AMR and listed in the appropriate tables of the LRA.
RAI 2.3.3.10 IA-2 Instrument Air
=
Background===
Drawing 2022 SH 1, Flow Diagram Primary Containment Cooling and Nitrogen Inerting System, shows a 1/2 inch pipe at location A-6 within the scope of license renewal and subject to an AMR and continuing on drawing 117C3317 SH 2. This drawing is not in the LRA.
Issue:
Since drawing 117C3317 SH 2 is not in the LRA, the staff cannot determine whether the applicant has appropriately considered the continuation of the piping on this drawing to be within the scope of license renewal and subject to an AMR in accordance with 10 CFR 54.21 and 10 CFR 54.4.
Request:
Identify the above listed piping and determine whether the piping is within the scope of license renewal and subject to an AMR. Revise the LRA accordingly.
RAI 2.3.4.2 CF-2 Condensate Filter Demineralizer
Background
10 CFR 54.21(a)(1) requires the applicant to provide a list of structures and components subject to an aging management review (AMR).
Issue:
In RAI response 2.3.4.2-CF-1, the applicant indicated that the components corresponding to the condensate filter demineralizer (CFD) system are in scope and subject to AMR include valve body and piping components, and are shown on LRA drawing 2049, sheet 4 (location B/C-5).
However, the staff could not identify these components in the provided location.
Request:
Provide clarification of the components that comprise of the CFD system and their spatial interaction with any safety-related systems. RAI 2.3.4.2 CM-3 Condensate Makeup
=
Background===
10 CFR 54.21(a)(1) requires the applicant to provide a list of structures and components subject to an aging management review (AMR).
Issue:
In LRA Section 2.3.4.2, the applicant states that the condensate makeup (CM) system has the intended functions for 10 CFR 54.4(a)(1) to provide water to the emergency core cooling systems (ECCS). The applicant states the emergency condensate storage tanks (ECSTs) and CM system components that support the high pressure coolant injection (HPCI) system pressure boundary are reviewed with the HPCI system in LRA Section 2.3.2.4. There were no specific CM components highlighted in a unique color designation to support this (a)(1) function.
The staff noted in the Cooper Nuclear Station USAR Chapter XIV, Section 6.4, the applicant credits the flow path from condensate storage tank (CST) 1A to the core spray (CS) and residual heat removal (RHR) pumps when the suppression pool is drained in response to U.S. Nuclear Regulatory Commission IE Bulletin No. 84-03, August 24, 1984. The applicant's evaluation concluded that upon a loss of refueling cavity inventory due to a seal failure, the CS and/or the RHR systems would allow the operator ample time to place fuel in a safe location per their emergency operating procedures. CNS Technical Specifications allow refueling operations to be conducted with the suppression pool drained provided an operable CS or low pressure coolant injection subsystem is aligned to take a suction on CST 1A, containing at least 150,000 gallons. However, the applicant does not identify CST 1A, nor the flow path from CST 1A (16" CH-4) as being in scope of license renewal from the CST until the reactor building, and only identifies selected piping (14" CH-4) in scope under 10 CFR 54.4(a)(2).
Request:
Provide justification of the exclusion of any components in the CM system for the scope of license renewal used to provide ECCS with water that are not included with the HPCI system.